ML20041C309
| ML20041C309 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 02/22/1982 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Vandewalle D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| Shared Package | |
| ML20041C310 | List: |
| References | |
| TASK-06-07.A3, TASK-6-7.A3, TASK-RR NUDOCS 8203010142 | |
| Download: ML20041C309 (3) | |
Text
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r February 22, 1 982 Docket No. 50-155 L505 02-084 e
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,,f,49 Mr. David J. VandeWalle 7
Nuclear Licensing Administrator G
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Consumers Power Company 1945 W. Parnall Road Jackson, Michigan 49201 L.,
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Dear Mr. VandeWalle:
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SUBJECT:
SEP TOPIC VI-7.A.3, ECCS ACTUATION SYSTEM, DRAFT SAFETY EVALUATION REPORT FOR BIG' ROCK POINT is a copy of our contractor's draft technical evaluation report on the subject topic. Enclosure 2 is the staff's draft safety evaluation of this topic based on Enclosure 1. proposes changes to the Technical Specifications.
The need to actually implement these changes will be detennined during the integrated safety assessment. This topic assessment may be revised in the future if your facility design is changed or if flRC criteria relating to this topic are modified before the integrated assessment is completed.
Sincerely, Dennis M. Crutchfield, Chief Operating Reactors Branch flo. 5 Division of Licensing
Enclosures:
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OFFICIAL RECORD COPY uso m im - -
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Big Rock Point Docket No. 50-155 Rev. 2/0/82 Mr. David J. VandeWalle CC Mr. Paul A. Perry, Secretary U. S. Environmental Protection Consumers Power Company Agency 212 West Michigan Avenue Federal Activities Branch Jackson, Michigan 49201 Region V Office ATTN:
Regional Radiation Representative Judd L. Bacon, Esquire 230 South Dearborn Street Consumers Power Company Chicago, Illinois 60604 212 West Michigan Avenue Jackson, Michigan 49201 Peter B. Bloch, Chairman Atomic Safety and Licensing Board Joseph Gallo, Esquire U. S. Nuclear Regulatory Commission Isham, Lincoln & Beale Washington, D. C.
20555 1120 Connecticut Avenue
' Room 325 Dr. Oscar H. Paris Washington, D. C.
20036
. Atomic Safety and Licensing Board U. S. Nuclear Regulatory Commission Peter W. Steketee, Esquire Washington, D. C.
20555 505 Peoples Building Grand Rapids, Michigan 49503 Mr. Frederick J. Shon Atomic Safety and Licensing Board Alan S. Rosenthal, Esq., Chairman' U. S. Nuclear Regulatory Commission Atomic Safety & Licensing Appeal Board Washington, D. C.
20555 U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Big Rock Point Nuclear Power Plant ATTN: Mr. C. J. Hartman Mr. John O'Neill, II Plant Superintendent
. Route 2, Box 44 Charlevoix, Michigan 49720 Maple City, Michigan 49664 Chri sta-Maria Charlevoix Public Library Route 2, Box 108C 107 Clinton Street Charlevoix, Michigan 49720 Charlevoix, Michigan William J. Scanlon, Esquire t
I Chairman 2034 Pauline Boulevard C'unty Board of Supervisors Ann Arbor, Michigan 48103 o
Charlevoix County Charlevoix, Michigan 49720 Resident Inspector Big Rock Point Plant Office of the Governor (2) c/o U.S. NRC Room 1 - Capitol Building RR #3, Box 600 Lansing, Michigan 48913 Charlevoix, Michigan 49720 Herbert Semmel Mr. Jim E. Mills Counsel for Christa Maria, et al.
Route 2, Box 108C Urban Law Institute Charlevoix, Michigan 49720 Antioch School of Law 263316th Street, NW Washington, D. C.
20460
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2-Big Rock Point Docket No. 50-T55 Mr. David J. VandeWalle
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CC Dr. John H. Buck-Atomic Safety and Licensing Appeal Board U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Ms. JoAnn Bier 204 Clinton Street Charlevoix, Michigan 49720 Thomas S. Moore Atomic Safety and Licensing Appeal Board U. S. Nuclear Regulatory Commission Washington, D. C.
20555 dames G. Keppler, Regional Administrator Nuclear Regulatory Commission, Region III Office of Inspection and Enforcement 799' Roosevelt Road Glen Ellyn, Illinois 60137 9
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SYSTEMATIC EVALUATION PROGRAM TOPIC VI-7.A.3 BIG ROCK POINT TOPIC:
VI-7.A.3, ECCS ACTUATION SYSTEM I.
INTRODUCTION f
The ECCS actuationsystem was reviewed with respect to the testability of operability and performance of individual active components of the system and of the entire system as a whole under conditions as close to the design condition as practical. The purpose of the reviews was to assure that all ECCS components (e.g. valves and pumps) are included in the component and system test and to assure that the scope of the periodic testing is adequate and meets the requirements of GDC 37. The technical specifications were also audited for large differences between the present test requirements and those in the Standard Technical Specifi-cations.
II.
REVIEW CRITERIA The current licensing criteria are identified in Section 2 of EG&G Report 0040J, "ECCS Actuation System."
III.
RELATED SAFETY TOPICS AND INTERFACES The scope of review for this topic was limited to avoid duplication of effort since some aspects of the review were performed under related topics.
The related topics and the subject matter are identified below.
Each of the related topic reports contain the acceptance criteria and review guid-ance for its subject matter.
Topic VI-3,
" Containment Pressure and Heat Removal Capability."
Topic VI-4,
" Containment Isolation System."
Topic VI-7,
" Emergency Core Cooling System."
Topic.VI-7.C.
"ECCS Single Failure Criterion and Requirements for Locking Out Power to Valves Including Independence of Interlocks on ECCS Valves."
l
-s Topic VI-9,
" Main Steam Isolation."
l Topic VI-10.A.
" Testing of Reactor Trip System and Engineered Safety Features, Including Response Time Testing."
l
\\e Only Topic VI-10. A is dependent on the present topic information for completion.
Response time testing is addressed in Topic VI-10. A.
VI.
REVIEW GUIDELINES The review guidelines are presented in Sections 3 and 4 of Report 0040J.
V.
EVALUATION Report 0040J describes the extent to which the ECCS actuation system is tested, except for the question of response time testing.
In summary, the safety systems do not ' meet the review criteria because of inadequacies in the current test program.
VI.
CONCLUSION Based upon our review of our contractor's evaluation, the sta'ff concludes that Big Rock Point conforms to current licensing criteria except for the Technical Specifications.
The staff recommends the following changes in the Technical Specifications:
1.
The Core Spray Low Pressure Coolant Injection Syster,: valves shall be subjected to a system level, no flow, test annually when shutdown.
This test shall demonstrate proper, automatic valve functioning while the pumps are locked out.
Upon completion, the pumps shall be tested to assure that tiw/ have been returned to service.
'2.
A similar no flow test for the Core Spray Recirculation System shall be conducted.
Proposed changes 1 and 2 above are consistent with past staff recommenda-tions in this regard.
The staff's judgement is that the system test frequencies are sufficient.
Our judgement is. based on operating experience.
The test frequencies can be changed if additional experience indicates that such action is neces-sary.
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